The NEA is organising the 16^th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...

The 12th International Conference on Nuclear Criticality Safety (ICNC) will be held in Sendai, Japan on 1-6 October 2023. Twenty years after the last conference in Japan, which was held in Tokai-mura...

In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...

The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

The NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...

The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...

The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...

Image: QUENCH facility at KIT. Court. KIT. 

The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.

The NEA has organised the first International School on Simulation of Nuclear Reactor Systems (SINUS) on the topic of Reactor single- and multi-physics simulations based on Light Water Reactor (LWR) ...

The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

International Fuel Performance Experiments (IFPE) is a data collection of nuclear fuel performance experiments for the purpose of code development and validation.

Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...

Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

EGPRS Task Force members met on 3 April 2023.

High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...

The WPRS met from 20-24 February 2023.

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...

The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

Expert groups on structural and fuel materials meet to advance materials science activities

Thermodynamic databases and accident prevention

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, an...

Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...

The understanding of nuclear physics and the associated uncertainties is essential to the modelling of all nuclear systems. Nuclear reaction probabilities, emitted particle energies and angles, fissi...

The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...

Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...

The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...

Courses were held in November 2022 in paris, France.

The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.

Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

TCOFF Phases

First Phase (2017-2020)

The TCOFF project established a framework for the exchange of technical...

The NEA Expert Group on Used Nuclear Fuel criticality (EGUNF) organised a Phase IIB benchmark to re-examine code and nuclear data performance for BWR lattice calculations and focus on the depletion m...

Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...